Clean and Sustainable Nuclear Power Srikumar Banerjee Homi Bhabha Chair Professor, Bhabha Atomic Research Centre 6 th Nuclear Energy Conclave, October 14, 2014
Clean and Sustainable Nuclear Power
Srikumar BanerjeeHomi Bhabha Chair Professor,
Bhabha Atomic Research Centre
6th Nuclear Energy Conclave, October 14, 2014
World Electricity Distribution% Population not having access to electricity
20% of World population (1300 million)
25% of India’s population (300 million)
Per Capita Electricity
Consumption in kWh
Earth at night
Near-Term Energy Supply– Indian Scenario
Meeting this requirement by burning fossil fuels (Coal) would result in 3-4 billion tonnes of CO2 emission
Solution lies in enhanced deployment of primary energy sources : Solar Wind Nuclear
9% Growth
8% Growth
Renewable + hydro potential
Currently Installed Capacity ~ 220GWe
66%
12%
19%
3%
Projected Electricity Demand in 2032
Population in India in 2030 : 1.3 Billion (lower bound estimate)
Per Capita Electricity Consumption to match present world average : 2500 KWh
Total Demand of Electricity : 3250 TWh
Total Electricity Consumption in 2011-12 : 770 TWh
India needs at least 4 fold increase in electricity consumption / production in next two decades
To control Carbon foot print capacity enhancement to be targeted
Solar : 5 to 50 GW 220 TWh per year 25% capacity factor (intermittent)Wind : 15 to 50 GW
Nuclear : 5 to 60 GW 450 TWh per year 85% capacity factor
Concentrated & Continuous Source
Distributed & Intermittent Source
Primary Energy SourcesFootprint for 10 GW Installations
5000 sq.Km
400 sq.Km
1 sq.Km
Wind : 25%
Solar : 20% Nuclear : 90%
Average Capacity Factors
Conversion from fertile to fissile materials
232Th 233Th 233Pa 233U
Fertile
4.5 x 109 y2.7 barns
Fissile
238U 239U 239Np 239Pu
23.5 min22 barns
2.36 days32 barns
2.4 x 104 ya 270 b ; f 752 b
22.3 min
1500 barns1.4 x 1010 y7.37 barns
27 days20 barns
1.59 x 105 ya 47 b ; f 530 b
Fertile Fissile
n
n
Fuel cycle options
Closed Fuel Cycle
FuelFissile+Fertile
Fissile partly spent
Fertile partly converted
ReprocessingNuclear Reactor
Fertile + FissileLong lived
waste Repository
Fuel Manufacturing
FuelFissile+Fertile
Fissile partly spentFertile partly
converted
Spent Fuel Repository
Once Through Fuel Cycle
Nuclear Reactor
Huge energy potential !!
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Adopting closed fuel cycle also reduces nuclear waste burden.
Radiotoxicity of spent fuel is dominated by :
FPs for first 100 years.
subsequently, Pu (>90%)
After Pu removal
Minor Actinides specially Am (~ 9%)
Natural decay of spent fuel radiotoxicity
With early introduction of fast reactors using (U+Pu+Am) based fuel, long term raditoxicity of nuclear waste will be reduced.
200,000 years
300 years
Attractive Features of Thorium / Thoria High Abundance
Uniformly distributed in earth crust3 to 4 times abundant than uranium
Better Fuel Performance CharacteristicsHigher melting pointBetter thermal conductivityLower fission gas releaseGood radiation resistance Dimensional stabilityBetter compatibility with coolant
Relative ease in Waste ManagementNo oxidation -Superior behavior Direct disposal in repository Generates less Pu and minor actinides
Proliferation ResistantSpent fuel difficult to divert for weapon applications
Minor actinide (g/T)
U235 + U 238
U233 + Th232
Np 900 3
Am 470 0.0018
Cm 220 0.00064
Minor Actinides in Spent Fuel
Sand containing monazite in Kerela (India) beach
Th based Fuels are attractive for both Thermal & Fast Reactors
U233 has excellent nuclear characteristics both in thermal and fast neutron spectrum.
Th is excellent host for Pu and enables deeper burning of Pu.
Using external fissile material U235, Pu or an external accelerator driven neutron source,Th-U233 cycle can be made self sustaining .
Deploying Thorium Energy: Three approaches
1. Thorium fuel in solid form in conventional reactors
2. Thorium as fuel in molten salt reactors
3. Accelerator-driven subcritical reactors using thorium fuel
KAMINI reactor in India (1996)
• 30kW experimental• U233 (20wt%)-Al fuel• Light Water Moderator
and coolant
• ThO2-PuO2 fuel • Burnup 18,400MWd/t
• UO2 fuel• Burnup 15,000MWd/t
Irradiated in Indian power reactor
Higher fission gas retention capability in ThO2 fuel
Thorium in Solid Fuel Reactor Advanced Heavy Water Reactor (AHWR)
AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water moderated reactor using 233U-Th MOX and Pu-Th MOX fuel, and Low enriched U with Th.
AHWR can be configured to accept a range of fuel types including enriched U, U-Pu MOX, Th-Pu MOX, and 233U-Th MOX in full core
Major design objectives
A large share of power from Thorium based fuel
Several passive features No radiological impact
in public domain
Passive shutdown system to address extreme threat scenarios.
Design life of 100 years.
Easily replaceable coolant channels.
Th-233U MOX
Pu-Th MOX
Inner ring:18.0% LEUO2
Middle ring: 22.0% LEUO2
Outer 22.5% LEUO2
Low Enriched Uranium (LEU)
Thorium in Molten Salt Reactor
Emergency Tanks
Heat Exchanger-1
Heat Exchanger-2
To Turbine and generator
Reactor Tank containing Fuel Salt under circulation
Reprocessing plantFission product removalAddition of fissile material
Minimal Waste : Online burning of long lived isotopes,Reduced higher Actinides
Safe : Liquid fuel, No meltdown possibility, Passive shutdown by fuel dumping
Efficient : Higher operating temperature
Thorium utilization in Accelerator driven subcritical system In a sub-critical nuclear reactor, fission neutrons supplemented by external supply of neutrons produced in a spallation reaction, High neutron yield (~20 per proton) Neutrons used for fertile to fissile conversion – Th232 to U233 (Fissile factory)
Incineration of long lived radio isotopes
Accelerator 1 GeV protonbeam
Spallation target
Subcritical reactor
Spallation reaction
15
Indian Prototype Fast Breeder Reactor
2580 1000
Fig. 4 -- PFBR FUEL PIN ASSEMBLY (all dimensions in mm)
30
Bottom Blanket
Middle Plug
Bottom End Plug
710300
10
Ø6.6
S.S.Wrapping wire
200
Spring support
Top Blanket
Fuel
5300
Top End Plug25
Spring
Core-1 (85)
Core-2 (96)
Radial Blanket (120)
SS Reflector (138)
B4C (78) -Not all shown
CSR- (9)
DSR- (3)
Core-1 (85)
Core-2 (96)
Radial Blanket (120)
SS Reflector (138)
B4C (78) -Not all shown
CSR- (9)
DSR- (3)
Core Layout
Radial Blanket (U238/Th232)
Thermal Power (MWth) : 1250Electrical output (MW): 500Fuel material : (U,Pu)O2 Coolant : Molten Sodium
Axial Blanket
U fueledPHWRs
Pu FueledFast Breeders
Nat. U
Dep. U
Pu
Th
Th
U233 FueledReactors
Pu
U233
Electricity
Electricity
Electricity
Stage 1Stage 1 Stage 2Stage 2 Stage 3Stage 3
PHWR FBTR AHWR
Thorium in the centre stage
Power generation primarily by PHWRBuilding fissile inventory for stage 2
Expanding power programmeBuilding U233 inventory
Thorium utilisation forSustainable power programme
U233
300 GWe-Year42000 GWe-Year
155000 GWe-Year
Indian Three Stage Nuclear Programme
Advanced Heavy Water Reactor (AHWR)Fast Breeder Reactor
540 MW pressurized Heavy Water reactor (PHWR)
Stage 1 : Power generation and building fissile
inventory for Stage 2
Stage 2 : Expanding power programme and building U233 inventory
Stage 3: Thorium fuel for sustainable nuclear
energy
• 2/3 energy from Thorium fuel
• Passive cooling and shutdown for safety
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Summary
• The Closed Nuclear Fuel Cycle can be a sustainable and environmentally benign energy source which can meet the base load requirement for the entire world for several centuries
• The Thorium – Uranium 233 fuel cycle is associated with significantly reduced radiotoxicity of the nuclear waste
• For the long term sustainability of Thorium – Uranium 233 fuel cycle a sufficient inventory of fissile materials (U235 and Pu239) needs to be generated
• Spallation neutrons from high energy accelerators can augment fissile inventory and can make Thorium – Uranium 233 fuel cycle self sustaining
Paradigm ShiftBurning fossil fuel Usage of primary energy
Forest Fire
Thermal Power
Fire Stone Discovery
Wind Energy
Solar Energy
Nuclear Energy
Thank you for your attention…